RCCE-E 2005 Creator of Confidence Between Nuclear Safety Authority, Owner, and Suppliers

2010 ◽  
Author(s):  
J. M. Haure
Keyword(s):  
Environmental Conditions ◽  
Nuclear Safety ◽  
Severe Accident ◽  
Frequency Variation ◽  
Electrical Networks ◽  
French Society ◽  
Low Frequencies ◽  
Custom Made ◽  
Nuclear Safety Authority ◽  
Design And Construction

The paper deals with the design rules included in the RCCE code applicable to electrical, and instrumentation and control systems and components contributing to safety-class functions. It is a major document in the relationships between the Owner and its suppliers and the safety authorities. The code is periodically submitted to the Nuclear Safety Authority Assessment. Initially used for the French PWR program and published by the French Society for Design and Construction rules for Nuclear Island Components (AFCEN), the code evolves to comply with third generation PWR nuclear islands and aims to comply with national regulations if needed in addition to French regulations. It gathers within one set of rules, the design and construction practices of, the electrical and I&C systems and components, and installation engineering documents. Brief presentation of some items is proposed: - Relationships between Safety Analyses Report plant system and installation engineering; - Off-site and on-site sources requirements; - Periodic tests and permanent monitoring requirements to guarantee the safety function availability; - I&C architecture and Human Machine Interfaces; - Digital I&C systems requirements; - Establishing qualification to ambience conditions, that includes normal and mild conditions and, harsh and severe accident conditions. Custom-made approach based on the families of ambience defined as a combination of equipment mission time, and normal and abnormal conditions (pressure, temperature, radiation) enabling to cope better with environmental conditions; - High and Low frequencies disturbances protections (Lightning, GSM, DECT, WiFi); - Project data used by any supplier or designer such as site data, temperature of rooms, maximum design temperature of equipment, the voltages and frequency variation range and tolerances of the alternative current and direct current electrical networks, the decoupling data of environmental conditions; - Electrical equipment separation requirements and isolation and decoupling solutions designs; - Electrical enclosures design requirements. A conclusion on the evolution of AFCEN organization in charge of comprehensive set of technical codes on the design, construction and surveillance of civil work structures, fire protection, mechanical structures, the core and fuel design, the electrical and I&C equipment and systems of PWR nuclear island.

Quality Assurance in the ITER Construction

2010 ◽  
Author(s):  
Sungkook Park ◽  
David Sands ◽  
Carlos Alejaldre
Keyword(s):  
Quality Assurance ◽  
Nuclear Safety ◽  
Quality Assurance Program ◽  
Roles And Responsibilities ◽  
Fusion Device ◽  
Safety Regulations ◽  
Nuclear Safety Authority ◽  
And Performance ◽  
Experimental Fusion ◽  
Iter Project

The ITER project is basically an engineering and construction project in order to build the ITER machine which is a scientific experimental fusion device. The seven members of the project have all created legal entities called Domestic Agencies to provide in-kind contributions to the ITER Organization (IO) for the supply of components which are manufactured by their suppliers. According to ITER agreement and due to nuclear safety involved in the fusion process, the project requires a license from the French Nuclear Safety Authority. One of nuclear safety regulations is the French Quality Order. The IO has established a Quality Assurance Program for the construction of the ITER machine to meet the requirements of the Order and to ensure that ITER activities are performed to achieve the safety and performance objectives of the ITER machine. The requirements in the program shall be followed by all performers involved in the project not only the IO, but DAs and their suppliers and subcontractors. This paper represents the quality requirements from the Order, and roles and responsibilities between each performer involved in the project. The paper also shows the main characteristics of the ITER Quality Assurance Program ensuring that all activities performed for the project conform to established and documented requirements.

Integration of Direct/Indirect Influences of Severe Accidents for Improvements of Nuclear Safety

2012 ◽  
Author(s):  
Kampanart Silva ◽  
Yuki Ishiwatari ◽  
Shogo Takahara
Keyword(s):  
Assessment Tool ◽  
Nuclear Safety ◽  
Severe Accident ◽  
Sensitivity Analyses ◽  
Source Terms ◽  
Fukushima Accident ◽  
Energy Agency ◽  
Severe Accidents ◽  
Level 3 ◽  
The Cost

Risk evaluation is an important assessment tool of nuclear safety, and a common index of direct/indirect influences of severe accidents as a compound of risk is necessary then. In this research, various influences of severe accidents are converted to monetary value and integrated. The integrated influence is calculated in a unit of “cost per severe accident” and “cost per kWh”. The authors must emphasize that the aim is not to estimate the accident cost itself but to extend the scope of “risk-informed decision making” for continuous safety improvements of nuclear energy. To calculate the “cost per severe accident” and the “cost per kWh”, typical sequences of severe accidents are picked-up first. Containment failure frequency (CFF) and source terms of each sequence are taken from the results of level 2 probabilistic risk assessment (PRA). The source terms of each sequence is input into the level 3 PRA code OSCAAR which was developed by Japan Atomic Energy Agency (JAEA). The calculations have been made for 248 meteorological sequences, and the results presented in this study are given as expectation values for various meteorological conditions. Using these outputs, the cost per severe accident is calculated. It consists of various costs and other influences converted into monetary values. This methodology is applied to a virtual 1,100 MWe BWR-5 plant. Seismic events are considered as the initiating events. The data obtained from the open documents on the Fukushima Accident are utilized as much as possible. Sensitivity analyses are carried out to identify the dominant influences, sensitive assumptions/parameters to the cost per accident or per kWh. Based on these findings, optimization of radiation protection countermeasures is recommended. Also, the effects of sever accident management are investigated.

E225 Unceasing JAPC's Effort to Improve Nuclear Safety against Severe Accident

2013 ◽  
Vol 2013.18 (0) ◽  
pp. 419-420
Author(s):  
Taku OHIRA ◽  
Fujitoshi EGUCHI ◽  
Masakatsu SUZUKI ◽  
Satoru FUKUYAMA
Keyword(s):  
Nuclear Safety ◽  
Severe Accident

IVR Model Study for Passive PWR

2012 ◽  
Author(s):  
Hong Xu ◽  
Peng Zhang ◽  
Zhiwei Zhou
Keyword(s):  
Nuclear Power ◽  
Safety Evaluation ◽  
Sensitivity Study ◽  
Nuclear Safety ◽  
Reactor Vessel ◽  
Severe Accident ◽  
Plant Design ◽  
Layer Model ◽  
Pressurized Water ◽  
Exterior Surface

1000-MWe scale Pressurized Water Reactor (PWR) is taking service or under construction all over the world, and larger scale plant is studied and developed for its more competitive economics. Not only design basic accidents are analyzed for nuclear safety, the severe accident must also be considered to meet with the increasing requirement of safety. In the “nuclear power plant design safety regulation” (HAF102) issued by Nation Nuclear Safety Administration (NNSA), aim at the preventing and mitigating of severe accident, the regulation bring forward new requirement, which required that during design phase, NPP should consider setting the preventing and mitigation measurement of severe accident as actually as possible. As an approach to prevent the curium from melting down the vessel and entering the containment when a postulated severe accident occurs, In-vessel retention (IVR) of molten core debris via water cooling of the external surface of the reactor vessel has been introduced into AP1000. External reactor vessel cooling (ERVC) is assumed to be achieved keeping exterior surface of vessel at 400K. It is known to all that different scenario and process results in different IVR molten model. As the core melt, different IVR model is formed at different time, such as two-layer model, three-layer model and four layer model. It is necessary to study the IVR model when severe accident process moves on. This paper studies two-layer and three-layer IVR models and find the features of the models. Based on this, sensitivity study of important parameters has also been analyzed. It is useful for us to understand the mechanism of the molten pool. This paper has some directive significance on future IVR strategy research and also provides theoretical support to safety evaluation of PWR plants.

scholarly journals ELECTRIC IMPEDANCE OF INJURED AND SENSITIZED RED BLOOD CORPUSCLES

1936 ◽  
Vol 20 (1) ◽  
pp. 105-109 ◽  
Author(s):  
Howard J. Curtis
Keyword(s):  
Electrical Properties ◽  
Membrane Permeability ◽  
Tannic Acid ◽  
Silicic Acid ◽  
Red Cells ◽  
Frequency Variation ◽  
Electric Impedance ◽  
Low Frequencies ◽  
Membrane Changes

On the basis of previous work on the electrical properties of hemolyzed red cells, it might be supposed that the variation of the capacity with frequency at low frequencies is an indication of membrane permeability. To test this, rabbit red cells were subjected to treatment with lecithin, tannic acid, glucose, saponin, amboceptor, and colloidal silicic acid, each in sub-lytic doses. No change in any of the electrical properties of any of the suspensions could be detected. The result may mean that the form of the frequency variation is an extremely insensitive measure of permeability and other membrane changes, and capable only of disclosing the very great changes associated with hemolysis, or it may mean that the change in the frequency variation at low frequencies has nothing to do with permeability.

scholarly journals The Sacred and Profane of Japan’s Nuclear Safety Myth: On the Cultural Logic of Framing and Overflowing

2021 ◽  
pp. 174997552110010
Author(s):  
Hiro Saito
Keyword(s):  
Science And Technology Studies ◽  
Nuclear Safety ◽  
Severe Accident ◽  
Binary Opposition ◽  
Cultural Logic ◽  
Policy Framing ◽  
Nuclear Disaster ◽  
Sacred And Profane ◽  
Accident Management ◽  
Fukushima Nuclear Disaster

Any policy requires a ‘frame’ and, by the same token, entails an ‘overflow’, externalizing a certain part of the world as irrelevant. This mundane business of policy framing and overflowing became an urgent matter of concern in Japan in March 2011, as the Fukushima nuclear disaster exposed how the existing frame of nuclear safety had permitted the fatal overflow of severe accident management. In fact, despite the creation of the new regulatory agency in September 2012, the post-Fukushima frame of nuclear safety continued to externalize off-site evacuation planning – a key component of severe accident management – until March 2015. To explain such persistence of the overflow, I borrow the concept of ‘sociotechnical imaginary’ from the policy-oriented strand of science and technology studies and infuse it with hermeneutical rigor of the strong program of cultural sociology. Specifically, I illustrate how the trajectory of Japan’s nuclear safety was decisively shaped by the pacifist imaginary and the safety myth, organized around the binary opposition ‘sacred = civilian use = safe vs. profane = military use = dangerous’, without reducing this deeper cultural logic of framing and overflowing to the political economy of nuclear energy or the global isomorphism of nuclear technology.

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